Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where Byoung Kwon Choi is active.

Publication


Featured researches published by Byoung Kwon Choi.


Metals and Materials International | 2007

Influence of ammonia on the corrosion behavior of Ti−Al−Zr alloy in 360°C water

Tae-Kyu Kim; Jong Hyuk Baek; Byoung Kwon Choi; Yong Hwan Jeong

The influence of ammonia on the corrosion behavior of Ti−Al−Zr alloy was evaluated in pressurized water at 360°C for 600 days. The results of the corrosion test indicated that the addition of ammonia accelerated the corrosion and hydrogen pickup rates. The oxide scales were composed of a double layer structure, and an inner layer was covered by an outer layer of oxide grains. The XRD studies on the oxide scales showed that the anatase-TiO2 was continuously transformed into rutile-TiO2 as the corrosion proceeded. When the same weight gain was considered, the oxide layer grown in water appeared to have a much higher rutile weight fraction than that grown in the ammonia aqueous solution. The deterioration of the corrosion behavior by the ammonia could be mainly attributed to the retardation in the transformation of the oxide structure from a metastable anatase phase to a stable rutile one.


Key Engineering Materials | 2007

Low Cycle Fatigue Behavior of Zirconium Tube under the Cyclic Pressurization

Jun Hwan Kim; Myoung Ho Lee; Byoung Kwon Choi; Yong Hwan Jeong

Study was attempted to produce stress-life curve of the zirconium tube under the cyclic pressurization and to analyze its behavior. The internal pressurization machine was devised and the low cycle fatigue test at the zirconium cladding tube was carried out. The result showed that the O’Donnell and Langer relationship can be fitted to the fatigue behavior of the zirconium cladding under the cyclic pressurization, where the fatigue limit of the Zircaloy-4 at 350oC was shown at 341.6MPa. From the analysis of the diametral changes and the fractographic observation, a combined creep-fatigue interaction rather than a pure fatigue had an influence on the failure of the zirconium cladding under the cyclic pressurization at 350oC.


Nuclear Technology | 2009

Effect of the Intermediate Cooling Process on the Behavior of the Zircaloy-4 Cladding After a High-Temperature Oxidation

Jun Hwan Kim; Byoung Kwon Choi; Yong Hwan Jeong; Seung Jin Oh

Abstract Studies were conducted to investigate the effect of the intermediate cooling process on the thermal shock behavior of Zircaloy-4 fuel cladding under a simulated loss-of-coolant accident condition and to analyze the related mechanical and microstructural properties. The Zircaloy-4 specimen was oxidized at the desired temperature and time, then various cooling processes were applied such as the direct water quench, the intermediate cooling at 700°C for 200 and 2000 s, and the successive cooling from 950 to 700°C. The results showed that the direct water quenching without any intermediate cooling process reduced the cladding ductility in that it reduced the minimum equivalent cladding reacted from 20 to near 17%. Ring compression ductility decreased, and the minimum thickness of the prior-beta layer thickness that causes brittle failure increased from 0.3 to 0.4 mm in the case of the direct water quench condition. As the cooling rate increased, the size of the plate inside the prior-beta phase decreased so that it induced an increase in the residual dislocation density to result in a decrease of the cladding ductility. Additional oxidation effect during a slow cooling below 950°C had little influence on the cladding behavior.


Journal of Nuclear Materials | 2007

Failure behavior of Zircaloy-4 cladding after oxidation and water quench

Jun Hwan Kim; Myoung Ho Lee; Byoung Kwon Choi; Yong Hwan Jeong


Journal of Alloys and Compounds | 2007

Effect of the hydrogen contents on the circumferential mechanical properties of zirconium alloy claddings

Jun Hwan Kim; Myoung Ho Lee; Byoung Kwon Choi; Yong Hwan Jeong


Archive | 2002

Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Sang Yoon Park; Myung Ho Lee; Cheol Nam; Jeong Yong Park; Youn Ho Jung


Journal of Alloys and Compounds | 2007

Mechanical properties and dynamic strain aging behavior of Zr-1.5Nb-0.4Sn-0.2Fe alloy

Myung Ho Lee; Jun Hwan Kim; Byoung Kwon Choi; Yong Hwan Jeong


Nuclear Engineering and Design | 2006

Effects of oxide and hydrogen on the circumferential mechanical properties of Zircaloy-4 cladding

Jun Hwan Kim; Myoung Ho Lee; Byoung Kwon Choi; Yong Hwan Jeong


Nuclear Engineering and Design | 2006

Effects of oxide and hydrogen on the behavior of Zircaloy-4 cladding during the loss of the coolant accident (LOCA)

Jun Hwan Kim; Byoung Kwon Choi; Jong Hyuk Baek; Yong Hwan Jeong


Archive | 2005

Zirconium based alloys having excellent creep resistance

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Sang Yoon Park; Myung Ho Lee; Je Geon Bang; Jeong Yong Park; Jun Hwan Kim; Hyun Gil Kim; Youn Ho Jung

Collaboration


Dive into the Byoung Kwon Choi's collaboration.

Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar

Jong Hyuk Baek

Korea Electric Power Corporation

View shared research outputs
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar
Top Co-Authors

Avatar

Kyeong Ho Kim

Korea Electric Power Corporation

View shared research outputs
Researchain Logo
Decentralizing Knowledge